IEC TR 61838-2009 Nuclear power plants - Instrumentation and control functions important for safety - Use of probabilistic safety assessment for the classificat.pdf

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1、 IEC/TR 61838 Edition 2.0 2009-12 TECHNICAL REPORT RAPPORT TECHNIQUE Nuclear power plants Instrumentation and control important to safety Use of probabilistic safety assessment for the classification of functions Centrales nuclaires de puissance Instrumentation et contrle-commande importants pour la

2、 sret Utilisation des valuations probabilistes de sret pour le classement des fonctions IEC/TR 61838:2009 colour inside THIS PUBLICATION IS COPYRIGHT PROTECTED Copyright 2009 IEC, Geneva, Switzerland All rights reserved. Unless otherwise specified, no part of this publication may be reproduced or ut

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16、 dsirez nous donner des commentaires sur cette publication ou si vous avez des questions, visitez le FAQ du Service clients ou contactez-nous: Email: csciec.ch Tl.: +41 22 919 02 11 Fax: +41 22 919 03 00 IEC/TR 61838 Edition 2.0 2009-12 TECHNICAL REPORT RAPPORT TECHNIQUE Nuclear power plants Instrum

17、entation and control important to safety Use of probabilistic safety assessment for the classification of functions Centrales nuclaires de puissance Instrumentation et contrle-commande importants pour la sret Utilisation des valuations probabilistes de sret pour le classement des fonctions INTERNATI

18、ONAL ELECTROTECHNICAL COMMISSION COMMISSION ELECTROTECHNIQUE INTERNATIONALE XB ICS 27.120.20 PRICE CODE CODE PRIX ISBN 2-8318-1071-7 Registered trademark of the International Electrotechnical Commission Marque dpose de la Commission Electrotechnique Internationale colour inside 2 TR 61838 IEC:2009 C

19、ONTENTS FOREWORD.4 INTRODUCTION.6 1 Scope.10 2 Normative references .10 3 Terms and definitions .11 4 Abbreviations .14 5 Limitations regarding the use of individual approaches alone .14 5.1 General .14 5.2 Limitations regarding the use of a PSA-related approach alone.14 5.3 Limitations regarding th

20、e use of the deterministic role-based approach alone15 6 Open issues regarding categorisation.16 6.1 General .16 6.2 Why categorize: To determine requirements, or do requirements determine the category? 16 6.3 To what degree are risk-based and probabilistic methods already used implicitly? 18 6.4 Ho

21、w precise do PSA results need to be?.18 7 Current practices in some member states.19 7.1 General .19 7.2 Brief summaries 19 7.3 More detailed explanations20 8 A survey of risk-related techniques of categorisation 23 8.1 General .23 8.2 Approach 1: Time and reactor states based approach .25 8.2.1 Cat

22、egorisation of FSE during the design phase .25 8.2.2 Impact of safety reviews on categorisation 29 8.3 Approach 2: Quantitative importance based approach .29 8.3.1 General .29 8.3.2 Quantitative assignment criteria.30 8.3.3 Quantitative criteria .30 8.3.4 Category assignment.32 8.3.5 Classification

23、procedure 32 8.3.6 Determination of requirements.33 8.4 Approach 3: Consequence mitigation based approach33 8.4.1 History: A dual licensing requirement leading to the probabilistic approach .33 8.4.2 Current probabilistic targets.33 8.4.3 Classification of safety-related systems.34 8.4.4 Application

24、 of design requirements34 8.4.5 Purpose of categorisation35 8.4.6 Categorisation principles .35 8.4.7 Categorisation methodology 36 8.5 Approach 4: Combined deterministic-probabilistic approach Bbased on NS- R-137 8.5.1 General .37 8.5.2 Basis for the historical approach38 TR 61838 IEC:2009 3 8.5.3

25、Plant state basis38 8.5.4 Defence in depth considerations40 8.5.5 Basis for classification Based on IEC 61226 .40 8.5.6 Application of IEC 61226 .41 8.5.7 Safety classification methodology42 8.5.8 Deterministic criteria for safety function categories43 8.5.9 Other classification considerations 44 8.

26、5.10 Worked example45 8.5.11 Conclusion 46 8.6 Approach 5: Application of risk methodologies in U.S.A. nuclear regulation.46 9 Comparison of risk-related categorisation results .48 9.1 CANDU plant stepback function.48 9.1.1 Problem statement 48 9.1.2 Solution using approach 3 .49 9.1.3 Comparisons w

27、ith other methods.50 9.2 Conclusions arising from the use of various approaches .50 Annex A (informative) The use of PSA: methods and results52 Annex B (informative) Approach 6: Role-Reliability-Timeframe based approach.55 Bibliography59 Figure 1 Historical plant states and allowed releases .38 Figu

28、re 2 Plant states and allowed releases 39 Figure 3 Reliability requirements for state transition barriers40 Figure 4 Categories required to maintain plant states 41 Figure 5 RISC Categories 47 Figure 6 Event sequence and layer protection identification.49 Table 1 Classification of I any IEC National

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38、it has collected data of a different kind from that which is normally published as an International Standard, for example “state of the art“. IEC 61838, which is a technical report, has been prepared by subcommittee 45A: Instrumentation and control of nuclear facilities, of IEC technical committee 4

39、5: Nuclear instrumentation. This second edition cancels and replaces the first edition published in 2001. The main technical changes with regard to the previous edition are as follows: to update references taking into account standards published since issue 1; to update the terminology; TR 61838 IEC

40、:2009 5 to take into account the progress done concerning the use of PSA for classification since issue 1. The text of this technical report is based on the following documents: Enquiry draft Report on voting 45A/766/DTR 45A/779A/RVC Full information on the voting for the approval of this technical

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43、hich are considered to be useful for the correct understanding of its contents. Users should therefore print this document using a colour printer. 6 TR 61838 IEC:2009 INTRODUCTION a) Technical background, main issues and organisation of the Technical Report IEC 61226 “Nuclear power plants Instrument

44、ation and control systems important for safety Classification“ was published in 1993, and revised in 2005 and 2009. The need to classify instrumentation and control functions on nuclear power plants now originates from an International Atomic Energy Agency (IAEA) requirement stated in Standard NS-R-

45、1, clause 5.2. IEC 61226 emphasizes that it is the functions, which must be classified early in the design phase so that the degree of importance to safety of each function is determined. At the design stage, I this is not the case in other countries. The release in 2000 of IAEA NS-R-1 and in 2002 o

46、f NS-G-1.3 has highlighted the requirement to factor engineering judgement and probabilistic criteria into the process of categorisation. For several years, how a risk based classification scheme could be incorporated into IEC 61226 to meet this requirement has been the topic of discussion. As indic

47、ated above, there are significant differences in the use of risk assessments throughout the world, which leads to several questions when drafting an International Standard, namely: 1) Should a risk-based classification scheme be acceptable in place of the deterministic approach? If so, what are the

48、requirements (especially regarding the standard of modelling and the validity of data) that must be applied? 2) If a risk-based classification leads to different classifications of FSE compared to the deterministic approach, which should take precedence? 3) Should the two approaches be used together

49、 in order to gain the maximum benefit? The deterministic approach is based on sound, well-proven nuclear safety principles, which people are comfortable with. Risk assessment results could lead to the classification of specific I&C functions being upgraded or downgraded (because of plant-specific design features). Should this upgrading or downgrading be limited in some way? 4) Should the use of risk ass